Scaling design and similarity analysis of a floating nuclear power plant

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-10-07 DOI:10.1016/j.nucengdes.2024.113624
Qingsong Liu , Yuexin Wang , Xi Deng , Chen Xi , Cheng He , Daoyi Chen , Huan He
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Abstract

In the process of developing floating reactor systems, their operation in the marine environment needs to be simulated to ensure the reliability of the safe design of nuclear reactors. Scaling test is a potential option for computer model validation by virtue of its low cost and flexibility. This study first gives the similarity law for dynamic tests of the reactor system in high-temperature environments by dimensional analysis. Then we focus on analyzing the jamming phenomenon that may occur during the similarity design process and provides a solution for realizing the contact state of the prototype in the scaled model. This study also analyzes the dynamic response of a floating reactor system under extreme operating conditions by combining numerical simulations and scaling tests. By comparing the response results predicted by the scaled model with the prototype response, it is further demonstrated that the feasibility of scaling test as an alternative to full-size test to provide a reference for realizing low-cost, accurate and safe design for reactor system.
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浮动核电站的规模设计和相似性分析
在开发浮动反应堆系统的过程中,需要对其在海洋环境中的运行进行模拟,以确保核反应堆安全设计的可靠性。缩比试验以其低成本和灵活性成为计算机模型验证的潜在选择。本研究首先通过尺寸分析给出了高温环境下反应堆系统动态试验的相似律。然后重点分析了相似性设计过程中可能出现的干扰现象,并提供了在缩比模型中实现原型接触状态的解决方案。本研究还结合数值模拟和缩比试验,分析了浮动反应堆系统在极端运行条件下的动态响应。通过对比缩比模型预测的响应结果和原型响应,进一步证明了缩比试验替代全尺寸试验的可行性,为实现反应堆系统的低成本、精确和安全设计提供参考。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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